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10 CFR 50.47, "Emergency Plans."
D.
10 CFR 50.54, "Conditions of Licenses."
E.
10 CFR 50.72, It Immediate Notification Requirements
F.
for Operating Nuclear Power Reactors."
Appendix E,  "Emergency Planning and
10 CFR 50,
G.
Preparedness for Production and Utilization Facilities."
Appendix I,  "Numerical Guides for
H.
10 CFR 50,
Design Objectives and Limiting Conditions for Operation to Meet
the Criterion `As Low As is Reasonably Achievable' for Radioac-
tive  Material  in  Light-Water-Cooled  Nuclear  Power  Reactor
Effluents."
I.
10 CFR 100.3, "Definitions."
10 CFR 100.11,  "Determination of Exclusion Area,
J.
Low Population Zone, and Population Center Distance."
USNRC Regulatory Guides, SRP Branch Technical Positions
13.3.2
and Appendices
1.97,  "Instrumentation for
Guide
A.
Regulatory
Light-Water-Cooled Nuclear Power Plants to Assess Plant and
Environs Conditions During and Following an Accident."
1.101,  "Emergency Planning and
B.
Regulatory  Guide
Preparedness for Nuclear Power Reactors."
C.
Regulatory  Guide
1.109,  "Calculation of Annual
Doses to Man From Routine Releases of Reactor Effluents for the
Purpose of Evaluating Compliance with 10 CFR 50, Appendix I."
"Emergency Planning for
D.
Regulatory  Guide
2.6,
Research and Test Reactors."
13.3.3
Codes and Standards
ANSI/ANS  3.7.1-1979, "Facilities and Medical Care
A.
(This
for Onsite Nuclear Power Plant Radiological Emergencies."
standard was withdrawn on August 10,  1987 and replaced by
ANSI/ANS 3.8.1-1987,  "Criteria for Emergency Response Functions
and Organizations.")
3.7.2-1979,  "Emergency Control Centers
B.
ANSI/ANS
for Nuclear Power Plants."
(This standard was withdrawn on
August 7, 1987 and replaced by ANSI/ANS  3.8.2-1987, "Criteria
for Functional and Physical Characteristics of Emergency Response
Facilities.")
13-6


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